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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARML20138E6191995-01-17017 January 1995 ASTM E136-94 Behavior of Matls in Vertical Tube Furnace. W/Rept Summarizing Results of Preliminary Tests Under Project 82NK21937,dtd 830926 & Ltr Forwarding Test Results Re Caulking Matl ML20209B5111987-04-22022 April 1987 Summary Rept for Davis-Besse Motor-Operated Valve Reliability Program ML20212M8171986-08-26026 August 1986 Test of Integrated Control Sys at Davis-Besse Nuclear Power Station to Determine Integrated Control Sys Response When Power Lost & Subsequently Restored, on 860317 ML20107B3061985-01-31031 January 1985 Rev 1 to Calculation M-8, Pressurizer Surge Line - Class 1 Piping Analysis ML20099H1181984-12-31031 December 1984 Reactor Containment Bldg Integrated Leak Rate Test ML20128N8361982-09-30030 September 1982 Performance Test Program for Increased Blowdown on Crosby 4M16 HB-BP-86 Pressurizer Safety Valve ML20063E2911982-03-22022 March 1982 Environ Qualification Rept 3394-2,Anticipatory Reactor Trip Sys ML20063E2351982-03-0101 March 1982 Seismic Qualification Rept 3394-1 Anticipatory Reactor Trip Sys ML20063E2731982-02-11011 February 1982 Seismic Simulation Test Program on Anticipatory Reactor Trip Sys (Arts) ML20039E6801981-12-18018 December 1981 Rept on 811209 Ottawa County/Toledo Edison Siren Test. ML20010G8621981-06-0909 June 1981 B&W Post-Test Analysis for Semiscale Test S-07-10D. ML20004C0871981-05-20020 May 1981 Suppl to Post-Refueling Physics Testing,Davis-Besse Unit 1, Cycle 2 Power Escalation Testing. ML19350A4291981-03-0505 March 1981 Cycle 2 Startup Rept for Facility ML20062J9351980-10-14014 October 1980 Analog & Digital Isolation Device Qualification, & Addendum a ML19337B6311980-08-29029 August 1980 Primary Reactor Containment Integrated Leakage Rate Test Rept. ML19260A2031979-10-0505 October 1979 Revised Pages to Initial Startup Rept, Suppl 6,covering 790706-1005 ML19259C7061979-08-0808 August 1979 Revised Pages to Chapter 1 of Initial Startup Rept,As Revised by Suppl 5 for Period 79046-0705 ML19319B8261978-05-26026 May 1978 Fire Confirmation Testing of Cable Tray Penetration Seals in Concrete Walls Utilizing Silicone Elastomers. Prepared for Util ML19329A9281978-05-0808 May 1978 Initial Startup Rept. ML19317F6341977-09-30030 September 1977 Confirmatory Testing of Fire Retardant Seals for Electrical Penetrations Through Fire Barriers Installed at Facility. ML19329A9051977-05-25025 May 1977 Fire Equivalency Test for Silicone Foam. ML19329A8101977-03-30030 March 1977 Conduit Separation Test Program, Final Program ML19329A9801976-12-22022 December 1976 Containment Vessel Integrated Leak Rate Test. ML19319B8241976-12-16016 December 1976 Isolation Circuit Test Rept. ML19329B1861976-12-16016 December 1976 Reactor Protection Sys Noise Testing Summary. ML19319B8251976-12-16016 December 1976 Cleveland Illuminating Co East Lake Tests. ML19319B8271976-12-16016 December 1976 Lynchburg Research Ctr Tests. ML19329C2141976-12-15015 December 1976 ECCS Emergency Sump & Pump Suction Line Testing, Final Rept ML19329C2991976-12-14014 December 1976 Hose Stream Testing of Bisco SF-20 Silicone Foam,Bisco SF-150L High Density Silicone & Bisco Flexible Boot Penetration Seals. ML19329C2051976-10-15015 October 1976 ECCS Emergency Sump Model Testing to Investigate Vortexing Potential, Interim Rept ML19319B8301971-01-21021 January 1971 Bailey Meter Co 880 Sys Count Rate Channel Noise Testing, 710104-21. 1995-01-17
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RPS NOISE TESTING SEUIARY -
1.0 Noise Rejection and Tolerance of the RPS The Davis-Besse 1 Plant - RPS exhibite a high degree of innut '.ty to the effects of. clectromagnetic and elect'rostatic induced noise on 'non-1E signal output leads and class 1E input leads. The immunity to noise is established by:
- 1. Operating experience
- 2. Tests
- 3. Noise reject!on circuits .
1.1 Operatine Exnerience The- RPS for Davis-Besse I is similar to the RPS operating at:
- 1. Oconee 1, 2 and 3
- 2. Three Mile Island 1
- 3. Arkansas Nuclear 1=
4 Sacramento Municipal Utility District The record of these operating systems shcus no cases where the RPS vera precluded from performing their safety function due to the precence of noise that exists at these plants. Additionally, there are no instanccc whera incdvertent initiation of the RPS safety function occurred due to the presence of noise.
1.2 Tests The RPS equipment van tested at the following test bcds to determine the system ability to perform its safety function in environments sicilar to nuclear power plants.
- 1. Lvnchburg Research Center
- 2. Cleveland Illumination Company - Eastlake Plant
- 13. Diamond Power Specialty Company These tests confirned the noise rejection circuit i.esign of the RFS.
1.2.1 .Lvnchbure Research Center (Attachment #1)
A cabinet containing the neutron flux channels uns tested for two years at
- the B&U Lynchburg Research Center. The channel processed simulated inputs, neutron inputs from a graphite pile, and neutron inputs from the Lynchburt Research Center pool reacter. I=portant modules tested uithin the cabinet were the linear amplifiers, bistables, system power supplics, and detcetor
. power supplies. The test. proved the ability of tha system to function as de-l signed in a simulated nuclear peuer plant ' environment. l 80.01300f8g l
s s.
,7 .
> 1'. 2. 2 Cleveland Illuminating Company - East Lake Plant Test (Attachment #2)
The East Lake Plant is. a fossil pcuer . generating station containing high electrical energy equipment. A cabinet containing signal processing equip-
.nent and bistables was installed for a period of two weeks. In this. test,
. the input cables were deliberatley routed as close as possibic to the electrical equipment described below to provide a severe EMI environment. The electrical equipment was operational and soce transient operation of the electrical equip-ment occurred during the test interval. During the test interval, the bistchle .
setpoints vere maintained within 0.020 volts of the simulated input signal.
The test results showed the channel generated protection signals when. required, no inadvertent protection signals were generated and no component "ailures were discovered. The East Lake test proved the ability of the system to function as designed in an environment considered nore severe than a nucles ,wer plant installation.
- 18 K VAC, 3,500 ampere main generator output busses
- 2300 VAC; 12, 28, 35, 38, 50,120, 230, 400, and 750 a peres circuits serving suitchgear, cable trays, =otors 480 VAC, 50, 60 and 115 ampere pcuer circuits and fan loads.
- 375 VDC, 930 ampera e:: citer
' 300 VAC,12, 35, 38 a= pere 11ghting, circuit pcaer circuits, crusher equipment, and electrostatic precipitators.
1.2.3 .Diacond Pouer Snecialtv Comenny Tests (Attachment #3)
Diamond Power Specialty Cc=pany provides the control rod drive control system.
The control rod drive system accepts 480 VAC, 240 a= peres and provides 125 VDC, 8 ampere square waves to the control red drive techanists. A cabinet containing signal processing equipment and bistables was installad for a paried of two veeks. In this test, the simulated input cables were deliberately routed as close as possible to 480/120 VAC,'250 KVA transformer, 120 VAC/125 VDC pcuer supplies, and the 125 VDC, 8 ampere square wave paaer cables. The signal processing codulas contained rate of changa c=plifiers and bist:bles. The test results showed the channel generated protection signals when required, oc inadvartent protection signals were genercted, and no cerpenent failures occurred. The test preved the ability of the system to function in an EMI envirennent containing 60 li: and switching transients.
'l.3 Noise Reiection Circuits The RPS' contains built-in noise rejection circuits to prevent icproper operatien due to signals induced by EMI. All digital logic is cade frcn
. relays. Transient voltages produced by EMI would have to have an a=plituda approaching the operating patential of the relay (15 VDC) and a duration long enough.(25 ncec) to cause the drop out of energi:cd relays. EMI induced trcnsient would have to bridge open ' control centact to cause da-energized relays to pick up. Relays are noted for inherent aoisa it= unity to trcesients
-induced by EMI. Analog signal patas are' eriginated with sensors that nrevide
.a current signal. proportional to the process par:1:eter 'conitored. The current signal monitoring method minimines the cifects of EMI. Additionally t.he utnalog signal processing =odules and'histables contain lou pass input 3$ "Y W
X e-filter'notuorks. : Typical _ modu'le _attenuat' on values for a 60 H signal are
~
i
. provids.d - below. When'the nodules are combined to form an instrument string, the combined a ' ttenuation'is realized. The lou pass filter circuit provide increased attenuation as.the frequency of_the E1I induced signal increases.
- The greater the transient rate,fthe greater the~ attenuation.
- The bistable module is .the last' analog signal processing module in an instrument' string. The bistable compares the measured process parameter
' to -a_ setpoint; if ' the setpoint is reached, Ja digital channel trip signal is it.itiated. The bistable provides the majority of analog signal noise attenuation,: location' of -the ' majority of the at tenuation at the end of the instrument string assures that noise induced upstream in the string from any
. source vill be attenuated by the bistable and produce minimum effect on the system operation.
liodule 60 H: Attenuation. db Buffer Anplifiers -8 Flou Summer .-13
'Heutron Flux Channel - Power Range -13.5 Square P.oot extractors -8 Bf ', table -34 i
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